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Harri Tuomisto
Harri Tuomisto
Senior Nuclear Safety Officer, Fortum
Email verificata su fortum.com
Titolo
Citata da
Citata da
Anno
In-vessel retention of corium at the Loviisa plant
O Kymäläinen, H Tuomisto, TG Theofanous
Nuclear Engineering and Design 169 (1-3), 109-130, 1997
2701997
Heat flux distribution from a volumetrically heated pool with high Rayleigh number
O Kymäläinen, H Tuomisto, O Hongisto, TG Theofanous
Nuclear Engineering and Design 149 (1-3), 401-408, 1994
1791994
Critical heat flux through curved, downward facing, thick walls
TG Theofanous, S Syri, T Salmassi, O Kymäläinen, H Tuomisto
Nuclear Engineering and Design 151 (1), 247-258, 1994
1281994
A consistent approach to severe accident management
H Tuomisto, TG Theofanous
Nuclear engineering and design 148 (2-3), 171-183, 1994
971994
Steam generator tube rupture (SGTR) scenarios
A Auvinen, JK Jokiniemi, A Lähde, T Routamo, P Lundström, H Tuomisto, ...
Nuclear engineering and design 235 (2-4), 457-472, 2005
802005
Corrosion of vessel steel during its interaction with molten corium: Part 1: Experimental
SV Bechta, VB Khabensky, SA Vitol, EV Krushinov, VS Granovsky, ...
Nuclear engineering and design 236 (17), 1810-1829, 2006
402006
Experimental COPO II data on natural convection in homogenous and stratified pools
M Helle, O Kymäläinen, H Tuomisto
Proceedings of the Ninth International Topical Meeting on Nuclear Reactor …, 1999
391999
Experimental and analytical studies of boric acid concentrations in a VVER-440 reactor during the long-term cooling period of loss-of-coolant accidents
J Tuunanen, H Tuomisto, P Raussi
Nuclear Engineering and Design 148 (2-3), 217-231, 1994
391994
Experimental data on heat flux distribution from a volumetrically heated pool with frozen boundaries
HT M. Helle, O. Kymäläinen
OECD/CSNI Workshop on Core Debris Retention and Coolability, March 3–6, 1998 …, 1999
31*1999
Experience from the first two integrated approaches to in-vessel retention through external cooling
TG Theofanous, C Liu, S Angelini, O Kymäläinen, H Tuomisto, S Additon
301994
Thermal-hydraulics of the Loviisa reactor pressure vessel overcooling transients
H Tuomisto
Imatran Voima Oy, 1987
291987
Commercial thorium fuel manufacture and irradiation: Testing (Th, Pu) O2 and (Th, U) O2 in the “Seven-Thirty” program
KI Björk, SS Drera, JF Kelly, C Vitanza, C Helsengreen, T Tverberg, ...
Annals of Nuclear Energy 75, 79-86, 2015
192015
COPO: experiments for heat flux distribution from a volumetrically heated corium pool
O Kymalainen, O Hongisto, J Antman, H Tuomisto, TG Theofanous
Proceedings of the 20th Water Reactor Safety Information Meeting, Bethesda …, 1992
171992
Critical heat flux on thick walls of large, naturally convecting loops
O Kymäläinen, H Tuomisto, TG Theofanous
ANS Proc. 1992 National Heat Transfer Conf. 6, 44-50, 1992
171992
Two-phase flow in a full-scale loop seal facility
H Tuomisto, P Kajanto
Nuclear Engineering and Design 107 (3), 295-305, 1988
171988
Long-term emergency cooling experiments with aqueous boric acid solution with the REWET-II and VEERA facilities
J Tuunanen, T Kervinen, H Kalli, M Komsi, H Tuomisto, E Markkanen
Proceedings of the international ENS/ANS conference on thermal reactor …, 1988
151988
Oscillations of single-phase natural circulation during overcooling transients
J Miettinen, T Kervinen, H Tuomisto, H Kantee
Anticipated and abnormal transients in nuclear power plants, 1987
151987
The development and demonstration of integrated models for the evaluation of severe accident management strategies—SAMEM
ML Ang, K Peers, E Kersting, W Fassmann, H Tuomisto, P Lundström, ...
Nuclear engineering and design 209 (1-3), 223-231, 2001
142001
Experimental studies of hydrogen behavior in ice condenser containments
P Lundstrom, H Tuomisto, T Lamberg, O Hongisto
121997
Experimental studies of hydrogen behavior in ice condenser containments
P Lundstrom, H Tuomisto, T Lamberg, O Hongisto
121997
Il sistema al momento non può eseguire l'operazione. Riprova più tardi.
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